ML20044B716

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Partially Withheld Commission Paper Informing of Denial of 791211 Request to Revoke OL for Facility & Related Relief
ML20044B716
Person / Time
Site: Berkeley Research Reactor
Issue date: 05/16/1980
From: Malsch M
NRC OFFICE OF THE GENERAL COUNSEL (OGC)
To:
Shared Package
ML19290F683 List:
References
FOIA-92-436 SECY-A-80-070, SECY-A-80-70, NUDOCS 9303030200
Download: ML20044B716 (52)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WAS HIN G TON, D. C. 20555 SECY-A-80-70 g

May 16,1980_

COiVIMISSIONER ACTION.

~

.. -.. The Commissioners For:

f Martin G. Malsch Froni:

Deputy General Counsel

[

DIRECTOR'S DENIAL OF 2.206 RELIEF (IN THE Subj ect :

MATTER OF THE UNIVERSITY OF CALIFORNIA AT

}

BERKELEY) DD-80-15 h

Triga Mark III Nuclear Research Reactor.

q Facility:

7 To inform the Commission of the denial of Purpese:

to revoke the operating license

}g a request for this facility and other related relief.

7 Review Time _

May 23, 1980 (as previously extended).

Expires:

11, 1979, the Friends of the Earth On Decer.ber Discussien:

(F0E) petitioned-the Director, Nuclear Reactor Regulation (Director) pursuant to'10 CFR 2.206 the reactor (1) suspend all activities at to:

operated by the University of California at (UCB); (2) order the removal of all Berkeley radioactive caterial from the site (Etcheverry (3) permanently revoke the current Hall);

operating license; and (4) hold public hearings before any resumption of reactor operation.

[ Attachment 1.)

F0E contended that the reactor's seismic design is inadequate in light of current seismological data and analysis, the potential threat to public health and safety is greater than previously estimated, and the current evacuation plans are inadeonate.

Support for FCE's petition has been received from the City Council of the City of Berkeley, the Board of Supervisors of Alameda County, and Assemblyman Eates of the California Legislature.

[ Attach-2.)

On April 14, 1980, the Dire.c. tor ment denied the pe.t.ition [ Attachment 33 f

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9303030200 921125 PDR FOIA GILINSK92-436 PDR

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k FOE centended that the UCB research resetor is 4

not designed to withstand the seismic stress 1

that may occur at the reactor site.

The reacter is now known to be forty yards from the main s

trace of the Hayward fault, not the three 3

hundred to one thousand feet assumed at the

{

time the reactor was licensed.

According te the United States Geological Survey (USGS), the i

active zone of this fault extends about three S

hundred feet on either side of the main surface j

fault trace, and an earthquake associated with i

the Hayward fault could reach a Richter magni-

?

tude of 7.5 to 8.5 Thus, the UCB reactor site 1

appears to be located within the active surface 1

rupture zone of the Hayward fault.

Morecver, I

recent lower magnitude earthquakes on other k

California faults have resulted in ground

}

accelerations far in excess of the ground 3

acceleration which would damage the UCB reactor even though those accelerations were measured i

at distances beyond the surface rupture cnes. 1/

i FOE ccr. tended that under these circumstances an

~

i earthquake on the Hayward fault could collapse the entire concrete shield structure (the patio

[

and the volleyball court) above the reactor,

[

send chunks of concrete and other debris into the reactor core, crush.the fuel elements, an'd

- j cause leakage of core material frem the 5uilding.

1 4

FOE also contended that a loss of ecs. ant accident could result in the release of large amounts of radioactive materials and thereby y

expose the dense population of the East Bay to a substantial risk of cancer.

Ecwever, the petition does not describe any specific accidents or estimate r adiological consequences.

e Finally, F0E contended that an earthquake en the Hayward fault would prevent immediate evacuation of the area surrounding the reactor because all roads veuld be blocked with detris.

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1/

Certain critical areas of the reactor are designed te with-stand a ground acceleration of 0 3 g while the remainder cf

~

the reactor is designed to withstPnd ground acceleratiCn if 0.2g.

The 1971 San Fernando earthquake of magnitude f.6 i

caused horizontal ground acceleraticn of 1.25g at a dist:nce o

of.8 km from the epicenter.

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3 lied on the

_In his denial, the Director re original 1965 Hazards Analysis and'the 1979 Safety Evaluation to conclude that an earthquake in induced design basis accfdent would resultThe 1965 4

acceptable radiological consequences.the Hayward fault Hazards Analysis assumed that 1s several hundred feet from the reactor site and that an earthq ake on the fault would in a maximum ground acceleration of a

result Although this acceleration could 0.5g. 2/

cause certain parts of the reactor to exceed stresses, staff believed it unlikely J

yield pointsuch an earthquake would rupture the that reactor ;;ructure or pool tank and lead to a Moreover, even if loss of coolant accident.

natural cooling by air coolant were lost, convection would prevent a core meltdown.

Finally, even if an earthquake were to rupture all walls and ceiling of the reactor room and a large number of fuel elements, the resultant exposures to the public would be within Part 100 guidelines.

4 The 1979 Safety Evaluation analyzed an earth-that assumes quake induced design basis accidenttotal-core disrupti of.0015 percent of the tc 21 core fission product inventory. 1/

Even if the building splits and releases the fission products toindividual thyroid the atmosphere, the resultant dose at the reactor wall would be a small fraction of the 10 CFh Part 100 limit, and the whole body dose would be negligibly small.

time the United States Coast and Geodetic Survey and an earthquake producing this 2/

At that the USGS advised the NRC that ground acceleratien might be expected to occur during the lifetime of the reactor and that the possibility of shear dislocation (relative sliding of adjacent areas of the surface) cannot be disregarded.

This number was chosen en the basis of research which 1/

that in the release of.0015 percent j

exposed to air will result of the fission products in that fuel element.

In the Matter of_

initial Trustees of Colunbia University in the City of New York,ALAB-50, 4 AEC l

~

610 (April 6, 1971), aff'd, Because the Berkeley reactor is lecated within

~~l decision, L AEC 594, the Hayward Fault Zone, staff assumed that all fuel elements could 349, $5h (1972).

fail.

.n 1

k Regarding emergency planning, the Director referred to the 1079 Safety Evaluation which states that the Emergency Plan conforms to the requirements of 10 CFR Appendix E, provides a basis for an acceptable state of emergency preparedness, and will be required to be revised in accordance with any changes in Appendix E instituted as a result of the current rulemaking on emergency planning.

Accordingly, the Direc-tor determined that the current emergency plan does not pose any u:due threat to public health and safety.

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C,s Re c omr.e nd ation:

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Martin G. Malsch Deputy General Counsel Comissioners' comments should be provided directly to the Office of the Secretary by c.o.b. Friday, May 23, 1980._

Comission Staff Office cor.ments, :l any, should be sutoitted to the Commissioners If the with an infomation copy to the Office of the Secretary.

NLT May 21, 1980, paper is of such a nature that it requires additional time for analytical review and coment, the Comissioners and the Secretariat should be apprised of when cocments may be expected.

015TR1LilTION Comissl6nEs Comiss%n 5t:ff Offices Exec D1-foe Operations Secretariat 4

1

FRIExos OF THE E ARTH i

1y

4 5n sk SAs Fnwc:cca C u.rensr s p res
n ag
a-O 4

1' i

December 11, 1979 1

r Dr. Harold Denton 4

Director of Nuclear Reactor Regulation l

Nuclear Regulatory Commission U.S.

h

  • 'ashington, D.C.

20555 n

a 4

University cf California, Berkeley j

RE: TRIGA Reactor; Docket NO. 50-224

Dear Dr. Denton,

a Section 2.206, Triends cf the Earth hereby 4

Pursuant to 10 C.F.R.

for Action to the Nuc' ear Regulatory Ccmmission.

I files a Request Specifically, Friends cf the Earth requests that the Nuclear j

Begulatcry Co:.ission order the felleving:

.=

Suspension of all activities under Cccket No. 50-224 1.

j at Etcheverry Hall, University of Califernia, Berkeley; 6

Removal of all plutonium and til other radioactive i

5

2. materia's and wastes fr:r. the Itcheverry Hall site:

I, i

revecation of.he Regents cf the University 3.

Permanent 50-224; j

of Calif ornia's operating license under Docket 50.

Holding of public hearings in the City of Berkeley ~

4.

j before any reacter opera-ion is resumed.

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{t Cn August 10, 1966, the TE!GA.V. ark Three ;cci-type nuclear reactor achieved critical fuel leading af ter the 7,egents of the University of California were granted an operatir.; license bv the 4

i Atcmic Energy Commission. The University research reactor operates S

at a steady power of 1.0 megawatt, and'is capable of a peak pulsed-i pcwer of about 2,000 regawatts. The reactor is 1:cated in a large laborator'f beneath the patio adjacent to Etcheverry Hall on the g

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Berkeley campus. Directly above the reactor is a et= pus patic and vollev. ball court. The reactor's cooling water and eentiIation s.es-tems flew through Etcheverry Hall, a six-stcry structure. Exhaust

,y f rem t.be reactor is also released en the patio level.

The Etcheverry Hall-rez cter ccmplex occupies abcut ene-half d

of the city block on which it is located. : rect 1 south of the

~

's reactor lies the University campus. Serrcunding the rea::cr en three w

f.

sides, to the north, east, and west, is ene of

t. e rcre densely s

ocula ted neic.hbcrhoods in Berkeley, censisting :f a large student 7

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populatien and an1 multi-unit res;dential dwell;nps.

.- the sare city block cs the reacter are seceral restauran::, sral'. sheps, a h)d!

and other businesses. The southea2: c:rner cf the

c. r e c e r v.
stere, and fu:ltd avenues cr:ss d

It bicek is a tusy intersection where earst e

l 5J at the North Gate of the campus.

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e This Rec.uest for Action is based ut.en the felicw;ne. : ens:-

7 i4 the reacter's seismic design is 1..adecuate acccrding' derations:

(1)

M to current seismological data and analysis; (2) the pctential threat,

to public health and safety posed by the reactor is ;reater than F

previcusly estimated; and (3) evacuation plans, in the event of a m

7, eactivity accident and/or natural disaster at the reacter site, E

b are inadercate censidering the reacter's site in a densely pcpulated e

4 urcan area.

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is roughly 40 The ma.n surface trace of the Hayward fault

.vards frem the reae::: size. Hayward f ault is an active, right-lateral:

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Accerfing to U.S. Geological Sur /ey analysis, the r

strike-slip fault.

active :cne c f the f ault extends :ut about 300 feet en either side i

cf the main surface fault trace. ~his active fault :cne represents occur in an earthnuai e the area in which ground surf ace ru.ctures ma".

i This may be a censervative estimate, l

generated by the fault system.

the maximum

'er data gathered frcm ver_dwide studies indicates that

ene width fer strike-sl:.p f aults may be much greater, c'apable of 2

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with confidence.

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. ear fau : bretks (less than 10 kilmetres distance)

.i accels-avai..able data and physical enderstandi.; indicate that 32:

a..! accelerations of j

ra.icns of greater than 2 g are possible, i

grcater than 1 g may be cc ecn."11 -

A::e'erations far in excess cf.5 g have been recorded duri.g several recent earthcuakes:

recorded

1. T!.e 19 71 San Fernando earthqua. e, magnitude 6.6, a distance of a km (accreximatelv.

1.15 g hori cntal et 1.es) frc= the epicenter:

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6.

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A.1 :. ce cf t'..ese earthquakes were smaller nan what we may expe::

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.3 Se: cgi:a1 5.:rve."'s 1974 analv. sis of this danger has been clear *.

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r The U.S. Geological Survey esiculates that gr cnd rup: re e

of as much as 30 feet is possible in a magnitude 8 earth uake On a strike-slip fault such as the Hayward fault.13 Ccn: ras: in

...is f

regard the design calculations of tra U.C. Nuclear Engineerin-Oe:t :

4 ment that the maximum amplitude of

- of the rea:::: c re in z:

earthquake could be no more than 3 inct.as:14 l3 akes i..o a -

A map prcduced by t.he U.S.

Geological Survey t

count 3 active fault systems (the Hayward, San Andreas, and Ca".avs a s

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which are expected to cause damage in this area. The rea:ter :.s

z. :.e 4

I, as within " Zone A" intensity. "2cne A" is the hic.hes: danac.e r a t i:.-

represented, and is defined as "very violent", ecmprising the " r e.fi.:

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landslides of great magnitude: consistent, deen, and ex: ended fir-l suring in natural earth."

Therefore the ecmplete destruction of the TR-A and its s u. -

l

^

vunding structures appears to b? a certaint'; : n a ma " or e a r

.qu e.r.s j

alene. the Ha.vvard fault in Berkelev. The e arth::ak e cu' d c:' '. an. s a 1

the entire concrete shield structure (the pa :.: and :he 1011e ba'.'.

i court) above the reactor. Giant chunks cf c *.:re e and c her debr:s would fall once the reactor cere, crushing the fuel e' e. ents and-l causing leakage of core materials f rem the bu:.'. ding, e.nd the.c os s ::. - ;

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be ignored.

l n.

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No nention is made of the seismic design est.ra:ss use d f--

i Et:heverrv. Hall in the Safety Analv. sis Report. Since pc:1 water it i

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is also dependent upon that structure, it is apparen- ::a: :.. e s a f t :-' t 4

of the TR:GA depends on the seismic stability cf I::.evi.;f Eall.

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5 later; and genetic diseases after exposure; cancer, 12 to 40 years and abnor.alities in future generations. Mest researchers bel: eve cause cancer and genetic defects.

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ses, radiatien.

in cca, arisen to a nuclear power plant.

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7_

IV. EMIBGIMCY FI?CSSES TO A TRIGA ACCICENT Tollowing a majer earthqua?.e on the Hayward f ault, all reads in the vicinity of the react:

would be blocked with decris. All emergency vehicles and personnel wculd be ik.mchlized. A substantial I.=ediate propertion of the nearby pceulaticn would be injured.

evacuation of the a_ea wculd be i possible.

V.

CCNCLCSION The NRC's continued licensing of the TR:GA reactor in the middle of a densely populated urban area is irresponsible. The reactor presents an extremely high risk to puclic health and safety.

Che reacter's site in the active rene of the Hayward fault and the cu: dated seismic design cf the reactor's pr:te :ive structures.makes pessible a serious radiatien accident. The inevitable result of such accidents is generous public expcsure :: radiaticn, causing cancer, mutatiens and birth defects fcr years := cene, and pessible permanent evacuation of what is presently much of the University campus and the city ' f Be rk e '. ev..

The reactor, ci.erating at its presen: locaticn, poses a clearly unacceptable thrsa: to public health and safety.

_r - _rT

3.,_r L r S. _r,

V..

1. Suspension of all activities under Docke: No. 50-224 at I::heverry Hall, University of Ca*ifornia, 3erkeley;
2. Re=cval of all plutcr.iu= and all other radicactive materials and wastes f rom the Itcheverry Hal* site revocatier. Of the Regents of the On:versity cf Calif:rnia's;
3. Permanent
erating licer.se c.. der Occke: NC. 50-224:

Holding cf public hearings ir. the City of Berkeley bef:re any 4.

react:r operaticn is resured.

.e s. e n.. s..,..,

g._.u_ _ i....a,

4 it '?b Y

liehe ?. aft;no,Lega. Assi.=: ant j

Trid" d1 of the Ear *h

~ j,ld'~<.l \\i.*$i.,*,s

/

k

t. M.

W. Ar.drewSaldwin,LegalDirec:(

Triends of the I rt:-

i

. r.r e_..r.. C r S C ".' r_ D I'.*

. ".'r.

"' 7 T.-

Zone l

" Map Shcwing Eecently Active Breaks Along the Haysarf. Tault and tne Scu hern Part of the Calaveras Faul: *one, California";

1.

Geole-i:a1 Survey, Map I-313: by D.H. Radbruch-Hall.

t 1974 U.S.

i Ocnation of the San Francisco Bay Region";1975 i

" Studies fer Seis..i:

Geclegical Survey 7:cfessional Paper 941-A; p. A-25.

2.

" Area Fault Map, University of California, Serkeley Fault Hazard":

3.

1973: by Ben Lenner and Associates.

I I

4.

1964 Saferv. Analv. sis :.eport; p.

1-12 Cenation of the San Francisco Bav Rec. ion";1975 fer Seisr.i:

a

" Studies 5.

Geolec.ical Surve' Fr fessional Pac.er 941-A; c..

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qeco.._-.. y

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. _ _, 4 and the Scu:hern ?ar: cf the Calaveres Fault Zone, Califernia";

e.

.c 1974 U.S. Geoloc.iral Servev,.va: :-B13: bv. D.H. F.adbruch-Hall.

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least locally extended as far as I km to several local geologv ar.d topegraphyt Recent fault :rt.ces along hat 2:

e!vmetres itheuse.ds of feet :o severai miles e from the strike s;ip faults such as :he San Ar.dreas c:.n be map-main fault iLamn ar.d othe-s.1905t Data from this '

ped more con 5dently than those on faults wi:h dip. slip and nur-erous other h;stua faulting events in the movement. Consequently, dip. slip faults mth y outhful h

w nr!d gne a tas:s for estimaung the !ccation.c aracter,movement are only now bemg recegnized in regions and manmum amount of g-cund deformation alcng where acave strike slip faults have long been k.own.

many ui the faults in the San Francisco Bay region.

Of pr.ncipal eencern in fault rela:ed ground deforma-2CNEklDTH tion are.1, detai!cd predictics of:he pattern of surface Although the nest obvious fault displacement tends fault:ng.especially the width ef the zone.t2) the amountto be localized along recognizable and mappable fault o: d:sp?acement a:rcss the surface traces of faults. and

@ tectonic d:stortion of the _--ound. including uplift.lineaments, some permanent ground deformation from fault movement extends outward from the =ain fault subsidence. and hori:enta! distort:en.

trace. This deformation, manifested as fra:*ures, HTTIRN OF SLRFTC1 T4ll. TING rebuvely small turf 3ce faults, and local warping, d

ld he The pattern of surface fauding. especial:y aiong the ' de 5nes an irregula str:ke slip faults involves a mam fault zone of varymg fa ult.

bu: p nerally nar:cw width along which the prme: palThe udth of this zene of surface deforrnanon varies dsets occur ar d lesser branch and secondary faelts with :he type of fauhing. earthqude capaude. the that estend to or occur at. eens.derable distance frorn local gaologic sett.ng. and perhaps other factors. An the ms.n :ene >5gs.12,15L Reserre faults ecmmonly example of this variat:en for s: :ka-sii;. taulting produce rnc,re cornplex rup:ure zones, and the zones associated with the Borrego Mountam enthquake is I

6 t p:cally are ircader and less regular in plan !6g 1 L shown :n table 3. Clark.19 2L Because the zone wid Ma;or displacemen:s c:n be expec:ed along ;mes-is +o var:able and because it seldom can be well de men:s de6ned by recogn::ab;e fault-caused topegraphic (muit event.

b:cres Sp 12.15, 5:ud:es of severalsurface fat.!nng, ty surface morpholcgy prior to nu mdic:te that h: ster:c g-cund ruptures closeiy de!ine.a onci tte acr.e. Such detaile:.te mformatten mappable gecmcrphie featur+s that dehneate w"ie!y availaole. In its accence, esumr.:cd tonow pwutun; fault : races #155 For-Tejen-Wilace.. is not u :

R based on companacn with known

9e 5.1906 San Francisco-La ason and otnes.1903. l zene w:cths are o enpatterns of deformation as 1959. 1066 Parkf.e!d-Brown and Vedder, documented modern fault geomet y acecmpanying W ailace, 1967.1c6F Ex ego Mountam-Cark and others.19 2.

major earthquakes.

f an Fer.ando--Yerkes and others.

Da:a on zone widths fer.'or h Arnercan es.heuakes N

Cari.19 2,1971 1973 Slana gua-Br:c. and othe-s.1973 >: these -

from 5 5 ta about d.5 were ec-ervations. :ggest that ;at: erns of surface faultmg, m the magnitude range 19 4 data are, pane tecause are predictac:e Cark 19 2) esuma:ed. for example, g analy:ed by Bonilla:1970..T sieng about 5-) percent of the length of:he surface i

idth drones : hat :an be ructure from the Bor-ego Moun:a:n earthquake of indies:e the general-ange n wke she faults. the man.um

52:
96s. tne pontmn sf
he mam surface fras:urcs could / anoc:parec. For str: width of the Ene. frc au.:

nee beee pred:cted :o wnhm about 100 m 1300 fu tor.e to w wier *dre 9 t. * %-m tone. :s about before :he ea-thquake. In the f an Tranctuo Say region.02 m.30m ft pt hahr fault = the tone :. a

.ueh a=

df

. These vn:ues are procabiy een.4emttre tne San Andreas. Hayward.Cencord. Antioch.an a ew at h-fau'.:s are m;.p;ed in 3ut?ic:en de:.sil to accurately ! 900 m 1003 ::

N T..ey have

.n.:w ine :ncar.en of fault traces.tnd of the expected l est: mater ex:est for ve v kr:e ear-tc d 'i g

t are ai<p.ac nenu Brew. and Efe.1071 Brown., Seen sug;eitec as tr.e

9 0; R chrah. Mia
McLaughlin. 1971:

should be u4ed caut.aua!y and w hete possib;e shu.*J be Much of this map mhence dec:sions on 'su piemented by 4::e msestigar 19 3. Bur <e and Hei:cy.19735

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UNIVI".51"i 0F

  • A:.* TOR.1A h

3ERCL.Y, CALITCRSI A i

~8 i

9 August 00 1*34 m

i h

Mr. Robert Lc.e-stein a

1 ApF :ca:::n 4

Division cf C:v11:23 h

U. 5. Aten.1c Energy Conr:ssten j

I w ashington *S. O. C.

t Q

Mr. P.icnsre 5:*sdr At t e r.t :c e:

l b

rear '4r. Silver:

1 to och anfor.atten :s sup;1:ed as Amer.cnent No.

1on Fer:nat Relatz-g to a Class 104 Tac 1&

The follew:ng i

Application for a Construe:

the Eerkeley Campus of tne for a Nuclear Reactor at (Ref. Doceet $0 224) ity License Universt:y of Cal:f ornia, Berxeley, Cal:forn2a is the previci. sly subz:s ted Reactor Saf ety Analysis' As stated E

-e-t o _ 21 se:stic :es:gn coef ficier.t of 0.20 g I

i "a

w it a 33 ;er cen:

r. crease in allosable stresses f cr the TRI~A Varx Ill reacter

-f has teen ad:pte:

In Order to prev ce sdattional saf ety strrcture.

n the ces:;n of :te sir.cture as a otole, critical areas (areas 1: 3hice. a fa: 1ere could cause a Icss j

s, of water fron ::e reacter pool) will be designed 1]

with a nigt.er 2--::e-i21 coeff c:ent of 0.30 g w:

n allcwacle stref.ses."

gl a 33 per cen: 1: crease j

e core and suppert structure have heen I'

Based on t his criteria, designe: to the 0.20 g va'.ue.

l The calculat:ces f er-this : enc:t en took tne f olico tr.g f orm:

1 ibut w:thou the cere acc.

11 The react:r tank full cf wa:er to ceterstne the response suppor: stru ctu r e l, sas araly:ed 0' l to a 0.2 g her :c-a; force.

!*.e result was a calculated.

f:r :ne ta k *::er.

l k

f reque ncy r es;cese

2) Tte ccre and su;; :: st racture :n :ne rescior tar.k tw::nou:

g

    • ter) sere analy:e: := cetersane ne respense to a 0.0 g *:

l t' l her :cntal f:r:e. 1; *as feund :a: :ne es;or ; art of ne 4 j 3eaght acts at the icoer end of tte su;por:

.t rue:.r e = ::r, cf a ;ene.12.s.

Oa-;;ng :s 3

occ::: cts apprea:r.

.g ths:

restra:n:ng force tr.rc..gh the cou; ling prev:ced by tr.e A fretuency rrspense was de:ert nel.

j

[

to t he tricge.

I n'

3) its core and su;::r: sir.;ct.r e we re analy:ed in the The l

reactor tar.x (w: : sater) fer a -ocoles respor.se.

'.$ 4C0 pas. The l

]

.antum stress v s calcula:ec to de5061 75 :1..::un is 21 is t

y e:d stress cc acn.sel ed

'ac:or :f r);gtly 2 c wr-l 40.000 ps:, ;;v :; a sr.: sty

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=:--

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1 - eW 51 2C. !!' 04 W-

.2-rh Er. Robert 14ws.5 Win

  • * * - J A L -t 27;'t!!t;.".g M ere,,*

[

calcultieO s*rell.

rescter c:221 :cr.s.

the

=ct:en :s :te.: J tr:*.es.

7 r yo.T

..nSs W:

d~'"f r &

. v per:CQ Cf :?.e react 0r Core and suppcr: stru;ture.: water otees r.ot att ain reso.

Iven if resor.a.co car.ce etin the.ater :-.ot;on.

ld stress, sere to occur ar.d : e J r'.:ture e ceeced the yieas the r.ater:21 yields, s

no f ailure.ould ec:;r to:3.ise it would relieve t..e stresses 3r.$ ut.synchron1:e the'ith the sater in the ta response of the Str'.:t' art Very truly yours, Hans Mark Chairzan. De psitzent of

. uclear Engineering N

31':1.'4 : b; o State of Cs;;:or::a)

J ss.

County ef. tis Wda i 3efore ae pers onally : 7= arec

. ;.e a
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:: *. t'.ere c: the CL7 of ze to :Se a;;e;&::c s set acG4.

l a n -'

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e 5:TE r/ALCA7;CN

?.

The propesed site f or the 77:CA Mark III re actor d:e s no

tese-t any spe
f,1 prehle:s frc: a hyd::I c gic al or =e te orole c ic a ; s ie.7e;,:.

gew,.er, the

,a, is Icca ted within several hundred f ee t of, :ne Ha sard 7aul: Syste: and wi: tin ateut 20 =il e s o f t he S a n And r e a s F a ul t. Lys_ir. e di=cassef the seis=ticg e )

g and ge ologic al characte ristics of this loca ti:n vi:5 re;te senta tive s if~ the e

y. S. C:ss: ard' Geede tic Survey and U. S. Ge:;e gical Survey, and have y,e3 advired than an, earthquake with a maxi gre.nd 4:ctiera tien cf 0.f g tight be ex:ected to occur during the lif e ti e of :ne f ac ili:y and tha t the pe, s g3 g..

11:y cf shear displace:ent at the re c tor lec a t ion c annot te dis:egarded.

I J Accordingly, we have evaluated the possible c:ns e quence s of an e a rthquake J

/vith the se r.a r i u: ef f ec ts, and have concluded :na: while certain parts of the s:rr s se r, it is unlikelv

/ reactor f acility cay reach or exceed yield poin:

2 J

/ that the s tre s se s oroduced tv ereund vibra t i:ns ~:uld te suf f icie.: :,~77---.e a rue 12 - ~4 r res u-k.

&;,:; c:re re...

/

'i~~'~7e~ a e t e r

.c....

l F7r:her, should core cooling be lost by a rupture of tne rese:c pool due to<

cif f e rential grcund rotice, eur calcula:i:ns ind ic a t e that natura; c :nvee:i:n ?"

j decay hea:-di 72 a ir c ec'. ing veulf._ic_! uf flt ie n t to prevent core <; tint due t:

y.ven 11~ 1: iJ assumed that tne groand d s;1 ace cn-due :: an eartnquake is 's (5 s

, revere enough to cau se rupture of a l a r ge nutt e r :l fuel e:ezen:s by =ce 33ni.

< cal da: age and siso results La rupture of the val;s and cei;ing of the reaeter 9

c:, the re sul ting c alcula te d e rposure s to tre putlic are within Part 1_C__._

- n s :.e r a t r- <. se nave :en:;;ced that tne si

. gu id e l ir.e s. ( cT. :ne!1 a s t s : :nese co is s u :a:Te~ f e r a reacter cf this t yp e a nd p e se r *. e v e l,

g i'

T.I ACZE F.CE'S I"r A L"A ~1 C N A TE!GA react 0r which is considered a pro!ctypt Of the 70!'A Ma rk III rea::ct has te en e;erating s ince Dece=ter et 1961 at :ne General At::i: Laboratory i: ~

i San Die ge, Calif ernia.

In additien, many other re ae:crs of the TE!CA desigts have been cons tructed and are o;< rating in a tanner s; ilar te that p re; c se d by the T iversity cf Calif:::ia, Zerkeley.

The e; era. g e perience with sie se reactor: ha s d e cons tr a t e d tha t the imp o r t a t t re a c ter pa ra me te rs c a n be co:fi.

~

destly predic ted.

Tha a pplic an t has ana y:e d various pc:estial ha :ards a s s e-c is ted with the ope ra tien of the re ac ter.

They i !ude (1) release of arg::-4:

(2) re ac tivit7 a ccide nta (3) fuel ele ent claddi:; f ai;ure, and (a) a 1:sa et c ool a n: ac:! dent.

Ladicaetive a rgen-41, which is produced f r:e s.eu:ren a::ivati:n cf the a ir in various exposure f acilities, eculd be release d :o tre reset:r roce and to the enviretsent.

Tie applicant's calculations and ur inde;enden analysis 1: dies:e that. rele a se of arg:n 41 vill n:: ex:eed tie C:r.certra:::ns s p e c if..- d 0: 10 C71 :f li=its f er res tric ted areas and f er :::-re s tri::ed a re a s vnier cec d ha oc c ap ie d.

The rese:ivity accide:: ccesidered by :he a p;i:st: is ass. et :: :::ar f:er delibera:e vi:la ti:n cf c;ers:ing pr:cedure s an: sever:1 inte r;::s s a.d scrart.

13 effec:, :ia ac: :ent c:na ista et inse r:i:; :ne f a.1 w e r '. : (

.e tra.ritt:

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NIVERSITY OF CAUFORNIA. SAN DIECO Y

pisco p s t h sc v 0

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NSUM;TE OF ntCPHYSICS # An PLANtTARYF4V5
C5,A-025 s:w*s issTruT;os oF c Lesochsv April 6, 1979 i

r lir. John Tar:akides l

U.S. Lepartsen: of Energ; Washington, D.C.

20545 4

Dear Sir:

respending to a request by Mr. Andrev 3aldwin, representing I a:

Triends of the Ist:h, that I cc=:ent en the seis:1c design appropriate for the Lawrence Livernore site. My cc :er:s are based on the geologic situatico as presented in the LLL repor: by L. H. Wight, "A Ceological l

and Seis:elogical investigatien of the Lawrence Liver. ore

  • aboratory-Site", and on present knowledge cencerning peak ground ace leratiens testi-e.xpectec very close to carthquakes, as presented in y recent

=cny bef ore the NRC concerning the Diablo Canyon Nuclear Power Plant.

This test':eny is attached.

The essen:ial conclusion of y tes:1:eny before the NRC vas that for large ear:hquakes (S > 7) ve do net have a suf ficient data base nor physical understanding to predict ground accelerations ver near r

f ault breaks (< 10 k distance) with confidence. Available data and i

physical understanding indicate that acceleratiens of greater _ than 1

i 2 g are pcssible and accelerations of greater than I g say be co en.

Cne aspect of the prcble: discussed in se:e detail in y testi eny, I

and which may be of crucial 1:pertance to the Livt :cre site, is the phenc enon of direttivity focussing of energy in the direction of fault prepagation. Ruptura along the Tesla f ault, as well as along-other mapped f aults in the region (in the direction of the Liver: ore r

It is site), could result in ano=alcusly high accelerations (> 23).

ot possible to ac:urately assess the probability of such an anc:alcurly

.g high acce'eration, but the ef fect is well established and co=:enly j

observed in rupture propagatics (see pp 3-10 to 3-14 of y testi=ony).

3 Also of parti:ular 1:portanca to the Liver: ore site is the conclusien of A breysey's that accelera: ions cf greater than'! g vill ;;c: ably be recorded f or even lov =agnitudes (p 3-6).

On April 6.

{

ions of.95 g and 1.C8 g, hort:en:a1 and verti:a1 components respe::1vely.

9de 5.5 shall:v ear:hquake in 1:an geners:ed peak accelera-1977 a agnt:

l (S - T 1 sec.)

i i

1

J. Tartakides 4/06/79 page 2 Another part cf cy testi eny which is of critical irper:ance to the Liver: ore site is the reported results fic: the Victoria Baja California earthquake svar= of March 1978 (Appendix II of :y testi=eny, pp II-l to II-7). One event of magnitude 4.9 produced accelerations of about.64 g at a distance of about 10 k=.

Althcugh final ir.ferra-are not yet tien on the cepth, locatien and rechanism of the event available, it nevertheless shews that even relatively small events of very can generate acceleraticas of ever.6 g in an environrent thick alluvium. This result indicates that the acceleratica value of.5 g taken in the L.. H. Wight report is not conservative.

Sincerely,

'Y ~ LL L b -%

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Janes :J. Brune Pr !ess:r cf Ceephysi:s J:.b : s d l

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SUPERVISORS I.

..h.

BOARD OF M,%

'NTY'o

.,W' t

October 30, 1979

.;O H N G C C A G C

...c ~. e.. n,. :..,..c, b

Dr. Harold R. Denten Director of Nuclear Reactor Regulatien U. S. Nuclear Regulatory Co::=tission 20555 Washington, D. C.

Dear Dr. Denten:

!s of f or Ac tion a d:i t t s -

I hereby endorse the Request p

t.ent the Earth to the Nuclear Regulatory Co=_ission which ruus.

ing ht*:rwe rsity o f Ca'.i f e r-it 's up revocation of the Reger-1.icense under Docket

o. 50-224.

Censidering the Etcr.everry Hall Reactor's :utiated seis:.ic design, cf adequate evacua-its site in a densely populated urban area and the

~at.

I sub it tra the Etcheverry tien plans in case of a radiation accident, Hall reactor poses an unacceptable thre'at' to public healt and safety.

to the 'Recte s t for Action to the Accordingly, I give fu'.1 supportI concur in the re:uest that all re-filed by Friends of the Earth.

.d i

aterials acter activities under Docket No. 50-224 be halted, al; n ioact ve _

N. R. C.

the reactor l

and vastes be renoved free, the Etcheverry 'dall site, e.:d that Cc nission.

operating license be renoved by the Nuclear Regulato:-

its responsibility. to I ask that the Nuclear Regulatory acksovledge i

on this Request the health and safety of the citiztes of Berkeley by a:t :3 up for Action.

V ry tru'y yours,

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ri G E'.EY C \\LU OMNIA 94704 (I;3) c4*-c M J:

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1979 Dr. Harold R. Der. ton Director of ':e-leer heteter Regalati r.

U. 5. Nu: lear :.e;.:la:Ory Cc='.s s ion

^

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tashingten, D. C. 20555

Dear Dr. Der:

cr.:

The Frier.35 cf th-Es.n h, 124 Spest S: er:, 5:r : =cis:c, Californj a, have requested that your Comission s sper.r c;l.;tc.:t:r a:tivity c.t Etchever y Hall, Ur.iversity of Calif-

.: at i;er

..*y a.C ne.e all plutonium a.. Other radiosctive. t eru! s.

He City Cou.:i1 of the City of t-n.s;

.ecise your 5.-

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UNITED sTI TEs

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NUCLEAR REGULATORY COM*alSSION e

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e'

rii 14, 1930

.9A

f. -

3 Docket No.50-22d s,.

J X

W.. Andrew Baldwin, legal Director Ilene Martino, Legal Assistant Friends of the Earth i

124 Spear San Francisco, California 94105

Dear Mr. Baidnin and Ms. Martino:

This letter is written in response to your petition, on behalf of the Friends of the Earth, dated December 11, 1979, re:;uesting the Nuclear Regulatcry Comission to suspend all activities under Decket No. 50-224, revoke the operating ifcense uncer Docket No. 50-224, order re. oval of all radioactive materials from the site and hold public hearings before any reactor operation is resumed.

For the'reasona set forth in the enclosed " Director's Decision Under 10 CFR 2.206" your request 18l

\\

hereby denied.

A ce;y of this determinction will be placed in the Comission's Public Document Fcom at 1717 H Street, N.N., Washingten,. D.C. 20555.

A ccpy will also be filed with the Secretary of the Comission for its review in accordance with 10 CFR 2.205(c) of the Commissioa's regulations.

l i

Er. closed for your inforr.ation is a copy of the notice that is being filed with I

the Office of the Federal Register for publicatien.

Sincere 1y, 6thk g

Harold R. Denton, Director Office of Nuclear Reactor Regulation l

Enclosures:

1.

Director's Decision under 10 CFR 2.205 2.

Fede-al Eecister Notice cc w/ enclosures:

See next page

I 1

i

  • vt/enciesJrEs*

i Frof Selig Ka;1an

eit: - 'd-ir.istre: r of i;uclear Er.gineerir.;

1

erart en

L.iversity of Califorr.ia a: Eerke.ey i

C:llege cf Er.;ineering Eerkeley, Calif:rnia

?'720 I

Mr. Michael Lawson f

Acting City Manager City of Eerkeley I

City Manager's Office 21E0 Milvia Street Berkeley, California 9470-f Mr. Thomas H. Bates f:e-ber of the Assertly t

California Legisla:ure Tweelfth Asser.tly Distri::

District Office 3923 Grand Avenue Oakland, California S?51 0 i

l Mr. John Geerge Alameda Cotnty Scarc cf Supervisors 1221 Gak Street, Suite 525 Cakland, Calif:rr.ia Sa612 i

6 b

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I

+

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E; E IE In t*.e M.atter cf

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}

NI VE
.5IT Y OF CAL 2FORNIA

)

D0ciet NO.

0-224 AT EERCELEY '

)

DIRECTOR'S DECISION U'1 DER 10 CTR 2.2D5 Ey petition datec Decem:er 11,1979, +.he Frienes of the Earth requested that an order be issued to the Regents of the University of California at Berkeley to suspend all activities of the TRIGA reactor at Etcheverry Hall, tdlhemove all radioactive materials from the site, :: reycke the, operating license and to hold public hearings before any reactor c;eration is resumed.

This petition has been treated as a resuest for action under 10 CFR 2.206 of the Commission's regulations.

Af ter consideration of the information submitted in the request by Friends of

ne Earth and evaluation of the issues raised, I have determined that the University c' California TRISA Mark III reacter d:es not pese any undue threat to the public healtn and safety.

Consequently, the request by Friends of the Earth is denied.

A copy of this decision will be placed in.the Commission's Public. Document F.cor et 1717 H Street, N.V., Washing cn, D.C. 20555.

Ml Harold R. Denton, Director Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 1:tn day of April,1920.

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..w By petition dated December 11, 1979, the Friends of the Earth (FCE) requeste d

4 pursuant to 10 CFR 2.205 of the Cm:.ission's regulations, that the Nuclear Regula-;

a tory Commission:

(1) suspend all activities un:er Locket No. 50-224 at E cheverry I

Hall, University cf California at Berkeley (UCE), (2) order tre removal of all radicattive caterials fre.- tne site, (3) perta er.:1y reveke :5e c eratir.g license,

?

cr. der Dc:te: Nc. 50-224, and (a) hold putlic hearir.gs bef:-e any rea::ar cperationl 1

is resumed. ' Feceipt of the petitier. was ackr.etle:;ed :y letter date:~ Jaruary 10 d

a

]

1920.

j r

The bases for the F;E's requested action -ere c:nten ':ns the: the seismic !

design of :he reactor at UCS was inade:uate based on curren: seismological data 1

f cnd analysis, the rotential th ea; to public hea' h and safety is ; ea:e-Fa pre:

i d'

viousi.v anai.v:ed and tha current eva:uation plans are inace;ua e.

S.

~

1 pf;er censideraticn of the infermatien presented by FCE, I *. ave de:errined, b

for the reasons se: fortn telcw and ir. the attached d::umerts, that tre re'. Asts l 1

5 fcr action should be der.ied, t

5 In the January 13,1FE" cri;{nal Ha:ards *.nalys's (En:lesure l' unter l'.te l t

s Evaluation (pa;e 3), the staf' de:umented its e.alcati:r :f :*e a#ft::s c' the les.

i

}

s of c:re c: cling ty a ru;:are e' tne re.::or :::1 a:en; w :. : e ru:: re of a large 3

i n u-t e r Cf **u el a *' a.e r.t s Oy '"e a n' C a l " a a g e a *.s a *. s: :*i #a*14"e C

" ' e e a l l s a *.

s, r

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The sta'~ ::nclude: tre

  • e ex; sure :: the p'.bli:

,5

..- - : ::: :ar i:: ;;idel;i.ei in: therefore a::e: able.

M re rece.;1y, en Ie;;e ;e-IE. li!?, :P.e 'JC issued a Safety Evalue:;cn and Environne.tal Impa::

f

aisa' s;;;;rtin; Ar.e r.

e n: No. 2 (Enci:sure 2). Inis anencrent authori:es con:irving c;e-ati:n cf tne UCE TRIGA Mark III nuclear research reactor. This Safety Eveiva:icn c cumen:s the staff's analysis of tne cesign basis accideri, a

rajor seismic even: leading to a complete loss of cooling water, core disruption and t-each cf the buiicin; walls (see pages 3 and a of Enclosure 2). The staff c:n:1uded that the radici ;ical c nsequences in the near vicinity of the reactor tc,1:- ; a e cf ne c-ce-of the l'ai:s cf 10 CFR Far: 20 (.*iornal Operational Cici:s) <

are are ;.ly a small fra::icn of ite limits of 10 CFP. Far: 100 (Accident Analysis Lini:5 f:r Sitir; React:rs).

I r. tre E e gency Fiannin; se::i n of the Sefety Evaluation (see pages 5 and f cf I.cics;-e I), :ne revies and acce::ance of the 005 plan currently in effect is d:cu e.ed.

Hr ever, tne Cornissien is currently up;-ading the requirements for E e ;entj : arning ty a e. ding 10 CFR Part 50, Secticns 50.33, 50.47, and 50.54 and

~

a;;e :a E as a resui: Of car review of the Three Mile Island accident.

'a* hen this l

~

r leratir; ;r0 cess is cot?leted, the licensees of all reactors will be required to r

revise Oneir E ergency Plens accordingly.

In cen:1u:Ter., ny review of the allegatier.s centained in your petition dated Dece :er 11, 1979, finds that sinte (1) the current desige issis accident for UCS i

esse es a co.;1ete loss cf cooling water, core disruption and breach of the building !

?

.ali: a-: res.1:s ir. at:e;;etle radicio;'c.

r nse:vence> and.

1ecurrentapproveq Ere ;e :

'ar fr ';5 re.s Our re: 're e '

'e L'ni,}rsity of California TRIGA i

L r

i

i t

i i

Mark II.T r:a::or c:es nct pese any undue threat to tr.e :ctiic real:6-a-: saft:y.

~

Tnerefcre, k find under 10 CFR Part 2, Section 2.205 :.a: ne prc:ee:in; on :te issues raised in y:ur petitics will be instituted in w':'e or in :ar:.

I A copy of this decision will be placed in the Ocm-ission's Public ?ccurent Rdom at 1717 H Street, N.W., L'ashington, D.C. 20555.

A co;y of this decision i

will also be filed with the Secretary for review by the Cc= mission in accordance with 10 CFR 2.205(c) of the regulations of the Conmission.

As provided in 10 CFR 2.206(c), this cecision will constitute the final action of the Commission j

t t-enty (23) days af ter the date of issuance, unless the Ccnr'ssi:n cr. its own t

rction institu:- s tne review cf thir decision within : a: ;ime.

t r

FCR THE NUCLE AR RE:-ULATORY COMMISSION W~

~.

a herolo R. Ler.t:n, D rec;or l

Gffice of !6 clear Rea;;or Regulat'.on i

Dated at Bethesda, Maryland inis 14th day of April, ICED 3

En 1csures:

1.

Ha:ards Analysis 2.

Sa'ety Evaluation and Environmental Impact Appraisal l

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....g y. < t,. e '. ' *. c k..* ^ =. s o n *. s e'r.s *.* e *.

a

. s; s.: -it ::p of the tech.

he reactor ct: te ::ved while the react:r is shut.

d: : e. d cperated at t.:y positics 0: t'.e track.

Sur cur. ding the peol is a.

c.... e 6,,, dd.e, s...c.~~-. vd..h,,...d e,s 'c. va *. *. u s *

.-a di a.'. a 3 '. a c

  • 1.*.*. *. e s,

s

.o -te. s1 c:1u

.s and seve.--si bete. ; orts.

Otter 1 re.dia.

an er;:su e ::::,

ti:: freilities in the ;:31 include a retary specimen rs.ck e.bove the core and s....,._ g.gso.sz.a.a.. a.se ec e, a.

o.

a _.

.. h.,.,.a...._...

s..,e y...

e.

..e te....., g.. * ' e s a.. s i-1'. ar *.-

t'.*.s e *...s +. a'.*.*. d

  • D t.e.-

a.

e,t.6

..LC...,.

l

...,,......... v., e., g 37,... -- u. e s. -. e.*.

  • v.e + v C.* L. c, 'y

.,.,........ e

..-..e, p.

...g,.... g.....,

y,.

1 s.e

.s

, g. g. y.. s.,.

t...,.

i

s.....
  • e......

.. C.. <w s* t.

A. t.

tra s<.e.,cd r'

... 9

....*s

., gr......

,.,..............=. 2e..s.. s.

g.... s =....

.a

.. ~...

,.... e. e. g, $ g g y.,.,.. y

.s. so a..,

A.., s.,

n

.a

.. g g.,....

...9

.u.

c,..

3...,. c...., e s... e.,. e..,.. g. s.

,y

....,y.,,y.,. g *

,y *.gc.g.a.... s.e

. e

.s.

+

i

=2o

.:.3....

..t...

3. g.s.j.,

.e..g.e c..

..,3

. a. y1..., e..e.,..

g. eys a

7......

._.......,.. a.g. e,

e,. 4 e.g.

3, 3e.. 3

.3-,.

.~

c..

3.w.gey3

.s

..ed by

., ". v

.,...c 1e.e.,,

.......n

.a.s. s.. a.e..a.,

..a s...,s. m.......

g.. a.....,,

....a..

r f a ilur: s,.anue.1 s cre., e.:1 e r -s tr.::.u stock.

tri.g the s ;uare-w.ve :.1,

,.......,. s..

e. 3 e t.: vd.'.' b e d.*.* *.._. e. e..

...e.- 'evel

,e.-*.

vd.11 d

c c..

,,. p. r. )

,. s.e

,2,,.,,ve se.....

....a.....,

9 o..

.....e..

.e,

...._.....,,...,1s.

. e.

..e..ed.

.9 e a..-.

.e t * *. d.-.r..". '..' S. e..- v' e.e s.,y

[

a

.a

.. e.rt. e. e...... <...x e.... + gg.,....,, e.

e..

3..,, -.e....... g, n,.

c 5.....e.,

e

.....e,...

t i

The c:re is located near the bett = et a large aluminu=.11..ed veter filled tank 1 :ated abeve the reacter rec = flo:r.

te react:r is eccled by natural c c:ve c.ie:.

'"te p;o1 vster is cooled by a recirculating vater syste: *tict pu=ps ;ool va.ter to a teat excht ger.

Secordary coolan.,vtich is at.ia higher pre s su. e the.: the recirculated pool vater, pe.sses throust the beat exchanger a::1 is pu-ed to a c:oling 1:v-r :n tcp of an ad'acent se::' n of the building, "he rer.cter vill be 5:used is a =ev buildir.g krevn e.s Etcheverry Es11 ytich is lo:e.ted : the certhern edge of the ce.: pus.

50 exclusi:: :::e vill be.s so c ' - ~. ~. d s ' '. *., *... e v e., *. *. e

.?'e u.. ~.~. ' c s D '..- *...". y,

v..

  • c.*.* s. e s '%.. e *.

n

.u is t: :.se the reser.rch react:r, vd.11 be c::sidered e.: ex:1: sic: e.rea and access o ::is ::.= vill te cc. rolled.

':te rer.cter roc: lies belev E-ade and is 1L3 feet 1 s, 73 feet vide, i. d tr.s a ceiling height :" Ik feet.

A es=;us

ti
is 1:etted ever the reactor re::.

i e

>..,sc.....

. n............, z p.,. e.

.f. 1s a

.,ec.

o., c.,.

s. \\., a.,. _..s..., c n, s. a e,..

to a tei;tt :f r.;;r:ximately eighty feet above g ade.

A c: cling tover is l

e...

.s

.~...

.... e. c.. e

~..

, <. 3 w_,12,..

3., _3. o e c e.,.*.... a.. '.. *. ' e

  • e e c *. c.-
d ct.ter facil.it'es.

Ye:tilati:n sys:e=s fans exts.ust e.t this r:sf level.

l

""te ve:tilati:n syste= f:: the Keutr: ies Iet: atory.".1.1 te ec=;1etely i

s e t -c.te *. := the other vent'lt.tien syste=s.

It is designed to naintsi:

.,. c...... a. a.. '. e.". ' y.. ea *..* v e,- e < s e.". *. *.. e.e,.. *.. o r :".. e.- *.

c::d.' ti::s.

All air (exce;t for that in the ex;:su e ro: ) vill be ty;4ssed

~

it :ug: a 14 k :" e.t s:1ute filters to re:.cVe ;erticles Over O.3 ni:rens tefere s

tel:.g discharged to the atmos; tere.

Associated with the re. ter ror: ventila.

ti:: ryste vill te a detector to monitor the re.diati:: level is the extaust i

gases.

Siculd the raidation levels exceed a ; edeterzined level, supply rnd i

er.ht.ust "t.ns vill cense to fu:ctics a.nd tutterfly valves vill elete to ser.1 off the ro::.

Ite rc:c ai.- v11.1 then te pur ed at a 1:.er re.te through a glove ter ve:tilatie syste=, threugh a :ter :31 scrutler and out the exhaust syste.: 1:cated es the roof of Etcheverry Eall.

  • tis pu se esi.nt: ins a <.getive j

pressure in the resetor rc: a.nd 1.asures that exle.ust c' acti eity is ;e.rf:r:ed l

a. a e....o, 9 a

..e

.a.,e.

.s 54 s ds1.....n.

0 1.iq..dd r.:1 solid.v stes fr:n the react:r fa:1;ity vtil be coilected a:i stored

~ ;r eve:tual delivery *. s a vt: e dir;:se.1 c::.: t.:t:r.

A P' EJ11:3 s';_- p ::. k l

..,.., Evts.ay,e.o.n va.e vas.e.,.. es.,_...

u..

.....,...s._..'a.n...._.,..

.i tics.

te c:LiL:d a:ed vatar vill be teld t; until the activity 12s decayed iel:v levele ;er=i.ted ":r dischar6e.

?

F b

~

S I TE E'.*A L';r T I C S The prepcsed s ite for the TRIGA Mark III reactor does net present any special However, the s ite

reblers f rc= a hydrological or cetecrolegical vievpoint.

is located within several bundred feet of the Harvard Fault Syste= and within

e have discussed the se istoicgies]

20 ciles of the San Andreas Fault.

abeut ar.d geolegical characteristics of this locatien with representatives of the c

i and Geodetic Survey and U. S. Geological Survey, and have been U

S. Cesst acvised than an earthquake with a esxirue grcund acceleration of 0.5g might bc exeected to occur during the. lif etite of the f acility and that the porribi-the reactor location cannot be disregarded.

lity of shear displacement at ccordingly, we have evaluated the possible consequences of an earthq'uake

.awith these mar t=um ef fects, and have concluded that while certain parts of the is u nl ik e l v _

s t r e.s s e s, _i t__

reac ter f acility cay reach er exceed yield point tD r -he nt.ne.sses eroduced by ground vibrations would be s u fli_e_ int _t n.rup tu r e

@ aw -s s t ruchu er pani +W Thus, core celtdcun would net occur.

Tu r t he r. sneeld core cocling be lest by a rupture ef the reseter pool due to i

d. f f e r e nt ia l ground motion, our criculatiens indica te that natural convection iir cec 11:g would te suf f icient to prevent core celting due to decay heat.

Even if it is assu=ed that the ground displace =ent due to an earthquake is of a large nutter ef fuel ele:ents by mechani-revere en ugh to cause rupture i

c al da:4 ge a nd also resul ts in rupture of the valls and ceiling of the reactor the re sul ting calculated exposure s to the public are within Part 100

ee, g u idel ine s.

On the, ba s is of the se cens idera t ions, we have concluded that the site is suitat:e f er a reacter of this type end pcuer level.

i 7

FEAc~;E v.CAF / ET A LL'ATION 7?!CA rese tor which is considered a prototype of 'the TRIGA Mark III reactor A

the General Atceit Labora tory in tas tee: cpe r ating since Le cecter of IC61 at f 2 n Oie gc, Calif ornia.

In additien, many other re acters of the TElGA desigts leen constructed and are c; crating is a sanner si=ilar to that prepcsed have by the Unive rsity of Calif ornia, Berkeley.

The opera ting experience with these de=:nstrated that the i=portant reactor para:4ters can be confi-reacters has dently predicted.

7te appl ic ant has analyzed ratious potential ha zards a sso.

ciated with the cperation of the reactor. They include (1) release of argon-41 a loss of (2) reactivity accidents (3) fuel element elsdding f ailure, and (4) coolant accident.

a ir i

Eadiesetive argen 41, which is produced frc= neutron activation cf the l

in varices expesure f acilities, could te released to the reactor room and to

.the envirense nt, The applica:t's calculations and our independent anslysis indiccte that release of arge:-41 vill not exceed the cencentra tions specif frd is 10 C72 20 licits ter restricted areas and f er cct-restricted areas which c ou*d be occupie d.

The rtretivity accident ccesidered by the applicant is astercd to cceur after deliberate violation ei cperaties precedures and severs! interio..sr and scrats.

tte accident censists cf inserting the full verth cf the transient In ef fcet, rod v ile the reacter 19 opersti g at a high steady poser with all control rods

i l

1 I

h.

I ce'-".'a....s, s~.~.. w ' v...

Et c...-

w

    • e 6gr'.'.a..

.a s". x. r.,. eve *.,

....,,4

.t,. 9ess s....r.

.o..8

.s.,.....

. w.e.e....e

.s.

e..

a..: 4..,., e..u.,.., u,. y.o.

.-f

  • 4 kg L,... X,..

e.,.....

y. e 4

..be

,,gy.d-g;.. 3co,...e.. w d......

7.

.a a.g g.a

.wg.

1

...a n i.... ex

..a f..

.w.

g,...

.u...e,.

_ ~.,

,e.....a...,

$. e.e.r. e.

c.,

  • w. g '..s.t.a.a

.a

.t,,...,........a.

y

..y...

..e o..

c a a.e

. s. t..e

. g.... s..... g g.a.

g.

..;.t

s. ess L. p.e.:r s

r---.

e

~.. ~ ~. ~~~ e..' '. ' e.. e '. e ' *..... s.

^

c ~...c e.

cle.dii.4 'ai.u e either Cne a: cide: postulated as credible is a hel ele:e::

I

v.. s.,,,., a c.' ' e... e.. s ".
4.... '....e*.'... c*

ave.s.

e.

a..

s,.~ 3....,.. 3.3.y etle excess ree:tivity (2.1%).

Assu=ir4 such en a::ide..: c::u-s, a signal fr =

f....

ventilati:n vould actuate da=;ers in the react:r r:::

the tir ::nitorir4 syste:

Any air ex;elled frc= the res:ter rc:= u. der there c::ditic:s vould ;. ass Dilutic: in the general building i

sys.es.

th-: ugh the purge syste= described previously.~ the c :s;tcre v:c..id rehce the eet telov exbcust e. d dispersi n 1:

eref:re,

tE:Lrd

.o 0;eratira the axi=u= per:1ssible fcr ur.rt wieted areas.

s

".. *. e v e..*. *.*.e cla d d ' ~ o* a e x,- *

  • e * ' o o *. -

.. s. 3 4.

e

...s.._.e1 c.

o

.s,.

.. e ~.a v do t e. s*. *.. - e.,-* - e. n '.. t.e. e s e. o.

u.

e,.,..

e.g<.

3.

%..,. o.s a '.a."~' e '. e '. '. ~ e v.. e *.. ~... d... -,e-e+.*..~

e..

.3

,e

..e s

, y a..e - a C e..*.. a' e '.e.-e...., s.... e d a*. '.6 0. '. '.'. '.. e

e. '....

r s..L s

.4. 3 C.st 73. yely...

s 3

~ 7. '. '.'*.

  • e..' s ur1 *. *.<., *, *. v, * '.,, t e'."a.c*

O*,

.%,......s 1. e "p *. e.'s *.* * *. C ** 'i. e *. e '.. ' s C.

y s......

4

o. e c. d. e. '.' *. e #.

'. ' *. e f..,.a*.. E_d "e P..ve 3

y f

y

.s

< n...g......ug l.o s e.

1.

3

.,..<v..

. e. a.

g +..... gg s.. e p...,a.

-e. s..e.S. s t s... t s.

e..,t1

c.... s..

e g

o.e

.'s.t a..e,d...

.s.1..s

..,.... e e*

. s.,.

...k 1.4 e e. t...s. e. t.a. s S.

s..

.~

v.

.....e e.....

8..e a 1 c$

.- e *. ur *. c ' a...,,... o +

.w.

s.

l

.. vo.. i d t e

. e '. '.... e. *. '..r... e e '.. '

  • . e.. w, e.. e.. e ;.. - " ' d 'w e ' *. =. s *.$ =..

I s..,..

7..

g

.n

.g,..,...e...e

.,.. e u.. ~..

........ -~

r.

~

td

. e..e. ex..e.

the.t required to react the y' eld ;cint of the steel cle.idire at the 3

1 4

highly unlikely that a fuel ele:e=t vould fail fell:ving an instartenerus loss t e:7e re..re.

dii feil he to everheatir4 If it is cssured that a hel eleze. * * " ' 'A ". ? '.. '. ~.~. *.... a 1 c f. : :1.-at e r.

c e.' e c *. &.' c '. e r..' s *. *..*. -. '....... -

e... s e

n..o a c..s.as.

f

    • te
ressre, the resultira ;otential vt
1e tedy and tyrc'd d:se rete
  • d A

. se.

3. e.. ' a *. ". '. e r t '..a.'. '. '~*

  • d. e *. o '. S. e.- e s t *. '.". '. *. v "...=... '.-.. a..- i.
  • E vever, calculations indicate that e. ;erse:ti=e to evacuate behre receiviri e e.t:ve.

suf*icient h a chare:s1 scrutter tr.ve ::re tha

.V.di;setive iodine in the air vould be clovly ;eged streutend c is:t.rd to the seneral public veuld te negligible.

l 7:e General Ate: irs Division of General Lyne.:ies Cor;;re.ti:n Les ir. :s11ed :. :y is tech.'etlly pelified to e::..

:-.* type rea:ters and demonstrated that itM.-k e '. e y '. e. s a. e s "..'. '.. s ' *...-

o. e,-. -. s e '. e s e "...
  • -- s ' ~. ~ e.- L'. '...o-- ~. '. =. N '. ' - c > A.". ' e 2.-

5....

.. e s t z. <.e.. s '-... s '. e.-. ~o I

s stEff and h?::i Os1 1

e7a s.s E...s..

100a* ed o3 *he Nrheley Ce.7.s.

g.

a reL:* r, Vtich 15

  • es.e.*

.c se*,

.n.s..-

.* a..e.cg...

n e. y.y nezve s y..,.s..

'~ *

~r--

u

. e v' e' a ' **

r t..,... a. u..s... t g a..

e.,. s C.,. e s t.4.. A ;e.....

g.g..J3 C.~..d *. e e % s * *. *. "* e '. ~ ~ '. '. '.

  • d.

.s

.. -. c. e >
  • r ~. ~. ' ~.... s.,.-. o. h. s.

. e t. c ~..~..~ t.- *. i v '. *. '. e s <... '. *. o s, ~.~ o.*. f.-.,. s *...,.g..e.

3

.s.g..e

........e..

s

.e

. e.....e

.J...

4 a

... g

..e g

..e

~

f...

l 5

e 5-

e. e.,...... n... w e...*

C '.' e '. & e.S C." -.. - - *..' e = s

.T S. e.v e c *.. - '.". ' *..' '. " * '. '.' *..- a. 's

-*=s-.*b'..

. -.Aw v. 3.g T...., g.s C *. '.

  • C*..*

C *..t* *".'C'.e.d. E..d a

g c..g..g

. sj. * *.. y...., g

<f..

g. c.4 C "' '. '.~ e

'L.'..# ~.~ *..- S.' '. V,

." # C3 '. '. #. * *. * *. E N. *. E. * '. *. */ C.S

~..'. s *=".~. '. * ".*. e.. '..*. *, a...

j 7..

r..yyg.,

s.e # *. t E3 C *y *. T S'.#. 4

~

4.

.v. S e g3. 3 g A gg a. g...

s.

.sg...k 14..

.w y s.

i 4

V..'.' '. e -. q". *. e '. *. O s.'..~_ '. *. s * *..'.1 O..'

1* ~ =. :s e *. 5 ' s E ". *. ^, '. '. ~. ~. s '.1. '....*.

4

..e ex.e <...s to $ee

..e :.....s.4

..e s....

.... t 4

.. s,

C *.** '.'.'. c *. *. #..

e P..u Ga W d

L B4x Ssul Levir.e, Cr.' et Test & ?:cer 7.etc*or Safety 3-anch

~

D' v' s i:r. o f Fe r.c r Li c e. sir.g g

D 13 P t

9 6

I e

f I

r 6'

5 b

i b

f P

k I

F F

L 5

t 6

5 b

i.

h i

,I 4

t h'

p:'.

c*u.c s.,

. o e,

NUCLE AR REGULATCRY CCWISS;O'J

_ f $, -:- (g h we se.:. es. c. c. ::tss

a 4' W. E c

iL/'

~

% ! 4,;x%,.: n p 5.F ~TY E'.'ut' TIC't A:O ET. :::*e'E',T:t :":: T : r:::H:

1

.......-y.- : ;. _.... e-

_ Y.... O,r.. C

-,, L,,.,,..,..,m: r.. e..

e art r

u r..
D FACILITY L::ENSE 'O.

R-101_

SUpF0F.TI :S A"EDE',T NO. 2

- - - :v.

r. r c.. u s-t,,.,,,Lc: e. Y C r ei

. 2 DnCKET 'i0. 50-??a,

Introduction tne University of Calif:-nia at Eerieley requestet 30, 1974, By letter cated Cecember that the Facility License No. R-191 for their TR]GA M In res;cnse to our requests, :ne lite.see ;rovided additional inferration in support of this renewal ap?licaticn by letters dated Fetruary 1 February 3, 20:5.

and ~ecember 21, 1976; August 15, 1977; and Te:ruary 5, A;ril 2 and May 14, 1979.

l l

u:date the existing specificaticns, are desigred to rte The =cdifications have been diacassed with and acce;;sd ty :ne licensee.

,/stuss3cn The TRIGA " ark III reactor at the Univer:ity of California is cf a design de The reactor.=.s firs by Gulf Ceneral Atomic, Inc.

for a period of ten years, as r.easured frem the c:ns:ruction ;e

~

Wt with a maxirc-reactivity inserti:n fer ;uised experimen<

(February 3,19E5).

The state ;o-er level of 1 ':A nuster of ciner TF.:1A Park II: rea t::r: have tien licensed to Fore:ver, ::nsider.

of 2.lt delta k/k.

c;erate at this power level and with nis reactivi:y insertion.

c;erating experience to date indica:es that the T;21' re :: r S

ation of the University of California TR:1A reactor in the manner curre a:curately predicted.

ty the license.

De s c riotien Us ;0sl-ty;e rese::r with fuci-coderator The TRICA Mark III reacter is a heterc;ene: ele ents. ace up of a r

2

era e a: 5:!ady hydride clad in stainless s: eel, and :Es.;ned :Ihis ty;e Of f a.d :frc:nic:

~

5:2:e ;;v.er levels up :C l mat.

f rea::fvity,.n.cn inre-egt,;y 1; 1 s the
r
;; necative ter;erature c:effician:rea:::r ;c..er to a safe lavel d is :esignd re is tusteaded On a s'* ud f*: a trid"e c hi:' rides en tracks tht* s:anac.*

~he

ne top of the tar.k.

Tne re!ctor can te 9Cve:

c:ert:E5 at 29/ e '. s '....,..

... c... :.. s :.....r.e.s,...o.....

,e..al 6..

.,. c,... e s.n : e..., s...........,.

...a es.

c.. _,s c..s

.... o c

..o

. e _,.

i. 3. i... e.. e., c. a n e y..,...

., rc.r 4

a

.. '. $7e.s.q g. *,7y e.

z. g e. i. s. a. g s. p.

sv.

nigh s led ?9e. atic transfer

$r,..

.a 9

s u....

z.

s;sti en rick at:ve. e

-"e a-d 8... p.., i.. -. 4.., *. i ^. *. t.

ir.

  • .na.

Csr a..

~..

~ P o.

s r

.r...

8. 4. c n w. e.1 ) -,-.i.
e.. c.. a l a.,..- 4.n C..e.
2..,. s. 4,. < e,. a.

s

4. *. a r.... r t. 3 ez..:,

e..

a..

2.... e <. r.

r.. 3. s...,

e Pisear:. reic: Ors.

reactivity werth of 4.;;

're c re 1:adin; Or: vices a axi-.m excessFeector centrol is furnished by thre atove c:ld clean critical. rack a-d pi.icn centrol reds wi:5 a t:tal s

f ateu:

t

..e..a ~ e..

r.

15 r.,e.

w

...e a.

.... e. j e r.... s. v.... w co.

a.

i d is cesigred to te

c.. :.... s~.n is a safety r:d during steady state c; erat en an for ;uised cperatidn.
9eu.Ta
i: ally rencve:

'ea: tor instr.rentation fer steady state C;eretion includes fou Reactor shu;dewn is to mor.itor, incicate, and c:ntrci neutr:n flux.causet b During the centcle ;cwer f ailures, manual scram, and earthevake shock. Fewer square-save acce cf operati:n, tne period s:rin is dist:trected.

Curing pulsing level scran occurs at 110t cf the full ;c-er setting.Reac cr shutd:wn

eration, n
rmal irstr.ren:atien is distenr.ected.ne.tr:n flux circuit c
s pr: viced by an 't:e;rt:e:

fr:n an icn chenber.

The c:re is 1::a:ec near the botte cf a large aluminum-iired wate Or rc:n ficer.

he reat: r is c:o'.ed by

o1 i
ated at:ve :Pe rea::The p::1 wa:er is c:: led by a recirculating water Secrndary c olant, natural ccnvection.

system ahich fur:s ;;;l w!*Er to a heat e>: hat.;er.

a ri;her pressure : nan the rs:ir:uiated col wa:er, passes

hrcush the hea; excnanger anc is purrec to a c:oling ::.er en

.nich is a an adja:en; see:icn of tre building.

il which is The react:r is t. used in a tui ding kncen at'Et:heverry :-:aNo exciusien :re iccated on the nor-Pern edge cf :he carpus.

i h reuses the l

witn tr e site;.: wever, the Neu:r:nics Lc:cra::ry, wh c research reat. r, will te c:nsicered an ev:'usi:n area a-d access

~

tris r:c will de cc.:r:it er.

of 24 feet. A s

icng, ~3 feet wice, and has a ceiling heign:

143 fee can;us petic is iccated over the reacter rocm.

The ventilaticn systen for the Neutrenics Lab:ra :ry is c:epletelyIt se;arate fr:m the c:her ven-iiation systems.

e with res:ect to artient!

s

e react:r r::a at a sli;.:1y r.egative pres urf:r : hat in the exposure roc =) i All air (ex:e;:

a tark Of a: solute filters to ree.cve ; articles ever 0.2 microns c:nciti:ns.

5, c '. a. c '.. '..1

.' e. c..= *. *..- -

rr:.;-

.. me,.

7.

....7,.

. g :..,. s t..a g u,n.. a...... u. g

.....'... r..e r a d.'..s. i c n l e.. 1 '.

4.3 g

.,,..,,..r

  • ..a In:ald the rac'ia:icn levels extsed a ;rece:ermi ed y.. i.,.. e.
e. ~... '. s.s..a.. e. <.. s.,. 5 a '. ) ; c e.s s,... z.... < - e.. g. s. u.....
.e ex.aust ;ases.

.a

. w e....

,i.r.o...

. e,..u,

.u u

s

..x

....s.4.,.s

,.,s.e,..

.a..n.no..

...., s.

..gf.3..

5,.3.,

.. ~....

.,. i. <, e.... e.......,. g

......c.

......g,....,<...,<., g,.,.,g.a.ys..g,.

e.

.u.,

.u,...:. a. r...,. a..... :,;3

>a, e..,

<..,g,<

,. =,.

...y e.,

,.n*.T.-l'.e*.*.,.,,.*...==.,-......-e..

i;; ret

!.i:uid a.c 5: lid. astes fr:. the reacter facility are cellected a :

f;r Ever. 21 delivery o a *25:e dis;cial cortract:r.

A D gallc... ;

..< :s a_.,a.l.,w<.e

.. y.

a

.c..,..a s.,

e...a.,-a.p$

r

,ee-n.e.'.

< =.......

c

.. e C.. *..*.....* *.. '. W 2 *. e r i s ~. e 'i i., o p '. *.... I.. *. a r. *. "4.' #. 't d

2 1 *. 2 '. #. " r..

c...,,, c,..~., ic

=.1$

n.t...e.-

e.

6.:.5,.z7.,

.e.

6....

e..

i c....f...,,.. -. p.,

t..
... 5 4 ;.i 3.

c.a.a r. c e d 5 :. :... : c., n. y :...... c...

s. :.... a., s.

s.

.cc;.....

.a. ne.

l

--ine,.r.

e...

tr.e Teacter Safe:y *nalysis Ee; ort f.iied with :ne C -istien,.ay 27,199.

c.

..y C '... ;- a. s <.+.. '.,n w e r e.. >. c a a. a.

r i..a. i l.v *. o - a. ^.. - e -.= '.. :...= c a.-5.. ~... =. e..

These changes are re:crie: i ar.nual :;erating r

anc f acilitate c;erati:n.

Ner.e cf these cnar.;es resulted in a cecrease in rargi s cf safe:y.

re;;rts.

The proposed Technical

ecificaticns (75) have been evie,<ad and revised recuirerents of the regulations.

Tre 5 generally incor.

to niet curren:

pcratesthe design features, characteristics and cperating conditiens des-cribed in the Hazards Sc=ary Eeport as u;de*ed.

C: ;rehensive surveillan:e re; irements er.d administrative cor.;r:is have been i :';ded to a:stre eari.v de.e: tion of any degradation of any cc ;cnents and will assure acceptable end re:vire safety reia'ed reviews,

erfor a.ce of safety rela'e'.a.ecui;ren
F. e... '. k.= =. r '. n -

' r =. c.. i.., r a e. t, #.. e...e n* s c e.. <

r..., s...

s.

.4 e

provide sufficient ir.f tr.a: ion to ;er-.it an c::assment by tre :: mission r

....y r

w;))

e. e..s * : a.g c *. :. y.
t. e. e. g.a c e..s e o. S.

1 a.

..w n :.

.e.s :a../.

w r....,...,..,

.y. e..s...

r.

1 ee.ze..

75 3.,i,.,...,<..u. 3 :... 51 c. r. t 6..,. v e., e e n licensed :o c;erate f r pericds up :: C years.

Fer:e. One bases and con-c '.. c '. r. ~ i..' r e < e e. *. * *. '. e <, a.~ a. '.y'

. =. *. a * #.... '.'..:*. - z. a.

'e '..=. '. ~ e.'. ', n c.a r o-....

'...*..". ~.=. '. t e e. a ". *. *

e. g.. 3 e r.a l,v s i s c a. =..." c.. ~. a ". y l '..,.. ~.. :. :.,

'n n.

..n.

. u. c. s.

g. 'i e, m t... s.,.a )

c..

.a. a.

v e, e. a,.. c..

] t. e s. $,., e,., :. n.. e., _.s e.. e :.<:..,.

eri icn at
r :le s have arisen durir.g over tr.ir:aen years Of tu cri:e:

.2 r.a. ". '..- a. s ". -". e '. i '..* ~- =. a r.

e. #.. " '.. *

  • c.

'..r. e. c #. s a #. e '.y i "., ( 2 ). =. v i.c e..'

r continued safe operation Of na reac :t and to related e:ui;ren: :: assurt ass.re tet; any sigr.ificant c:rgonen: :egraca*.i:n di te :stec'ed in a Pis : :e als:

ave censide-atie

' ely ra.ner, ard (2) c ner T:!*a rea:::rs cf :

e > y.. '.... c =. a.......* e v,.'e r....a

.. #. a. v

..~ s..s. '. -....e. _s,

e-

..> ~. e c. ~ -

d d

c

.e.....

c =..> '... g-c i;ted ina-.he..,ve-sity c,. Call,. :rn.a at.-e se,.e

...a react:r can c:ntin.e s

cr.

,, e..

... s a. e

-..e.n e r :o r., r e e,u e s.. d.-. :.,,..e. c.

n.

s e.

... e 0,. 2. a., s.,

z..

o

  • he es:i a*E

.;se#ul life ci the fa:ility c:nside-atices. ',ae have ccncluded tha:. e en.g o..s.e ren,~.es.a.s. :

ia..se

,g :cg.

a. e e. r. e..,

r

~

.r

.n <. q s ex...a,. s.., e.

s.

is acce::at'e.

ft:.) a reactor safety stand;0 int the proposed a e-t en 7.e acrst case ecc# dent ;cstulated f:r a R: fa:ility is a fuel eie en:

In :ne.nlikelj e.e-t cf fat'cre wi n resultan; release of fission pr::; cts.

~

en ac:icer. a sicnal from the air teni;; ring s vez -tuid a:.a:e ca ;ers st:.

. u,v.n. e <. r.

. a. d. '.. r..-:.

L:-.--

e

..t

,,,C...

, e. 4.1. '. c r. < j~ c...

.. e t

e.
  • c 4 *. #. ^. *. s w
  • J' d -
  • s s *. 'a - *. ". ".n *. '.. t.. z *...2'..".'.

i..~.~."..

'n e

a.

^

.J

,t e.

2.

a e c e.. c,.

z.c.i ge3 n

m*.,

n--r-es-a-

,c-t

. e e. e e.,. 3 u...-. e - s y g. < -

4

.r.c...

..d.

ss.

r

. C. ;./1.,,.,.. i..- 6., ;.,. w.,.

-.x

,.e.-.s.e

a. '.- r e

s.

^.....e....:

$.s. :,..,

.,..?..

.g

.g sr g.......

.:s s..

e.

..e.,.

k

.:s acci:ent.

The wh: e t:dy d:se ra:e to a pers:n in ite rea:::r r:: sh:rtly i

ciaccing failure a f:er infinite :;eratien at 1 P.t af.tr a cE-- ai eli en:

as tie, c: ser.a:ively isti-a:ed at 150 niiliter :er 5:ur. well telcw 10 CFR i

r,..

-n l :.

2.. s.

1 he rea::ikity accident :ensicered by the a:;1icznt is ass. 5d to ec:ur as j

a ". ~. ~.. e n,v '~,~ '. c i i a. o.

..:.....~..:..n...

. c.

,.,.L. :. c. v -~.n.'.- *.c.

w...-

.c..

..i.,. z.

. c c. e. w..... o.,a 3.s Cf

~.

2

.u.

.6

...,i,;,.s......

s.,,....e.

3.

A,e<.e.t.

.o

.,,,...,I inse-:i g :.e full acr:n of the transient r-d while One react:r is c;erating In su:n an event, the a nign staad/ ;;ser with all control reds cut.

ata;:l': ant's cai:ulatiens, with hich we ::ncur, indicate that the aximum i

'e. : era:ure in :ne hottest fuel eierent would be less nan ECC'C ar.d tha:

ne axic.um pressure within the eieren; w:.ld be a;;r:x#:ately 5 atrospheres.

T9e resulting stresse en :he claddir.g will not exceed the yield stress at 500*C.

'We c:nciule that this terperature and pressurr. would not cause rupture of the feel elements.

Althcugh i: a;: ears that complete icss of pool water is unlikely, the effect

f 5.cn icss has been investigated. The applicant and we have calculated the axi um te perature to be expe::ed within :he hottest fuel element after a Iuc:en less of ;;cl water.

These calculatiens shcw that peak te ;eratures w uld Fan the elting terre ature of any part of the fuel element.

te 7.ch ':.er :

ur..e, :ne ir:ernal p.essJre generated w:Uld te Iess 17an that required to T

On rcac

ne yield ;oint of the steel cladding at the eleva ed ter;erature.

tisis Of *hese calculations we have c:n:ivdec :nat it is highly unlikely

. r. E a fuel eli ent would fail follcair.g an instantane:us icss of ;:ol water.

h2:
f it is ass. red { hat a fuel eieren did fail due t: cverheating be:ause of a :ledcing deft:t which existed prict to the buildup in intarnal pressure, the res uitin; ;;;ential whcie becy and thyrcid dese rate would be sc ewtat higher eve to the reactivity insertion accidunt discussed abcve. Pcwever, tran the:

ca'c.laticns indicate that a ;erson in the reacter reem w uld have rcre than luff':ico: :ite to evacuate bef:re re:siving a cricus exposure.

Eadicactive ic::.e in the air would be 51 *1y pur;ed through a cnar cal scrubber and diluted te':-e rea:hing any occupied tree cu side the building, and the ha:ard to the

e t il
.:lic would be negligible.

In accitien to the fere;cing accidert antifse s and be:ause the Uni.ersity cf

-e rkeley..lu.3 faci. i:y is 1cca te,. in t.r.e Fayward Faul: zone, is s

Ca...

  1. 1 :rn:a a:

a :tsie.n tasis at:ident analysis was perferred. that assures total c re_djs.

ru:::en ith c:ncomitant release of 1.5 x 10-3 pe-:ent of the.ctal cor 2

fis sion pr: duct inventory (Cecisien ;f ASLAS in the Matter of.,.

ustees of Col. zia University in the City of New Ycrk, May 18,1972).

The parareters us ed in :he ana1ysis are:

....,,,' ark 1 1 2

e r. 4

-eic :r -ty:e 3..,.

e. u.......e....

...e. s..y,'.
c
":s al :ateres Tissi:n Fr:cuct FElease:

1.5 x 13~2*

n 0.: =,ste

.., x
r:.:.: ;..z:a:

..........,z.3 3 x S.p..t s c,./, n;

.r.......,,-,.i. g.

.g;~,,4,:..$.

.<ce. g...,.,,.. 7 7 e-e 9

/j I

7. 5 R a.-

Tnyroid:

. -,,. :. a...,,.

, n.,. 3 ;,..

a a

c...
4..., g,. a 4..* '. '.= 2. x c >. "..
  1. . r a i r.

a *. s-c. - - =.. e.

~~=

..,'. i '. s.'..d r *.1 u. c. a. s f i s s '..~ r.,* r.. ". s *.

1.. i i a.. e, 2,

'.. star:ane:;s F.tiease Asssred t

Ear; 100 lici:.

Puted thyoid. dose is a small frac:i:n cf the 1

.FR The c:

.ne wnele d.v dcse is negligibi.v s. a,1.

u d

i

'*e '.tve c:ncluded, using a;;repriately c:nservative release fraction of a ajor seis -ic even: leadine. to reta:r iogical :::eline., nen in tre t ser:

treacn cf.he :uilcing d

a c:r;1ete less :f c cling water, core cisruption aninity cf t'.e react:r building i

walls,the radici gical censequences in the rear v c20 ard are cnly a small fra::icn a-e c' :he erdar of the limits cf IC CFE Par cf :ne lir.i:s of 10 CFR Fart 1C3.

. ~. "s.' a.. c a.'... a '.

. *.. e. s '. s. s

'c'., I C. '. o.,..-. i i c =... s e a. inspections' cf eten 'uel elem

/.. e.. =. r '. ' '.e d
2. 2.' r > *. v, file e :.e require ent f:r ar. ; 1 ie :narge in fuel

~nis is based en the fact Inst there Es been ro sas.rt:di that tne eit-t?

s. e., _..,,... o,.

.<..3.,es.. e

a..

n e' i 4..

d.rit; a pulse is the x.e..s.,.

3d 6ased on.s.e

,_s, c.

r..

o rei:tivity irsertec.and the excursi:n the f;e1 ex: erie-ces a..

4 any ;ressure ra-treter hat will affect the f;ei clateing, fuei te :eratu l

is and the

erati
ns of similar t);e TRW reac::rs.

s # n. #. #. #...$ *. '../ '

  • c - *..* > a..'..e,...2.+'

o#.

r : up r!.is-e:

is r.> i..ai ar.d wil'1 'n actiCn. this C a ge will 'p ea:ly recu*e y

... e. se.. a *.. *, a.

. -.. e. e. '<. s *.., e.- c o.... 'a c ' u s *. d %s. "..5.'.".."".Y

"...'...:. *. '. r..* c i. a..* -.

=.1 el :.. e r.'c

ilk :: f.el ele en: cistcrti0n.

. t

.. c.. c :.. r,.,. y.. s. 5 c. a. e s a c

a. s., s..,..

e..

?r:grt-tas :eer resie.e' and found to l

~

s 1

i i

e li:ensee's C; erat:r Kequalif cat :n te acceptable.

.Fi a.cial Consids*atiens

~

f Califerr.ia'

%e have e. valuated the financial qualifica:ic ir

..s.. s...

C.,s o<....ss.o c.. erg

, e.. :.,. s.

. e...

s

(..a.. a.. n,

2 r

a,.e..n o..T reV<.EW o.. s..,.

e.....,....a

, a... n..

a.. g e., r.,.

s.

s J.

a. $. t. a (.
2. g ) 4

...e.

e..,n g..

o

..,..:

  • f
s... e. s.

..g

.a..,C..(

g a., s.g $ s.y.

n.

..., e. $ g 7y.,.,, g '..s v.,.

e..c'.

.e..

..-e,.i a.d

\\

r:s

c. a......

..a s u.eg. g

a. - a. s.. s.. t,.,.. J :. r a..ee..s a.s.

..~.: % :,..

s a..

e.

  • in.a e..::. : a.. : n.

e

..,. 1x...,

.6 s

.. s... :... y : *.. 4.1 c

y a..,

..a

....4.,..

....e e.c.c.

..s..

2 t.

9

s. e

.6 e.,,

. t...,.., y :

  • a.
r.. s
e. s... s....

<..s......:........z..

c.e.e.

c s

g.. (s.A..$:...$ <......:

. r..

.. s.

    • ].

. e.

e.s. s.

. c.

  1. ... c*.* * ~.g
  • ..,.a..

2 1,

1

  • *.c..
  • ,
  • g.

J..,.. g /.

,;w

.. :..... i..

s

e rs:;i e ents cf 10 Cf; ;;;endix E and
.:T ure that it c:nf rms ::

ecness.

It sh:uld

-
vices a tasis 'cr en a::E;;2:le s:::e f e-ern-e.y ;rt:arss; rev; sed and when in cr1:!-fa :f *::encix ? is :e effec:ive, :ne licensee ii te -e: : ed to revise :ne Emirgency Pian t e.::t d t' 4.1 c c
  • a :::r ti r.;1y.

Security Plannire 18, 1974, We teve re.ic.ec the current securi:y :lan s;tmitted Sc;te-terac:ectable to tee:

20, 1975, and find i:

trd "evision i da:ed Decetter

50. Se::icn 50.34(c) i1d 10 CFR Part 73,
ne re;uirerents of 10 CTR Pa :

inese documents and our evalua tion,fincings are in th Commissicn practice, This amencren:, in keeping with curren:

aeds a parrgraph to the license which identifies the currently approved CTR 2.790(d).

ser..rity p'.an and inc:i::ra:es :he plan as a c nditicn of the license.

I J:ncluti_cn on Sa'ety i

c:ntir. ed :; era;{cn Of *Me reector /ces not involve ee teve c:nc.sc'ed that 1) sign;ft:an; ir:rease in :ne ;rcia:1;ity or c nse:ventes cf accidents and

~

a sigr.ificant ha:ards

es not decrease the safety ar;ir and : Pere is n :

the health and safety I

i'deratien, E) there is reastntble assurance

-2:

by c; era ti:n in :he carr.er pres:rited

ne ;Lblic 111 not be encangeri: con:inced c;e a: inn of :ne reacter will not be 3r.imical
by :te T.S.,and 3) the heti:h end safety of the public.
..nz c:nr:n refe :e and se:gri:7 er ::

?! Envirenren:a1 In:ect *::-tisai

h c;e ation cf research reacters has

'ne environ. mental ir:act a:sc-ia e:

tem: rand *.m (D. Fuller to D. S'(:vholt,

een generically evaluated ir. a staf-see Safety E.!1uati:n cated April 25,197?, for the
e:ed Jar;ary 28, :?72,
  • b. 5;.59).

Inis e.:-indum c:ncluces tha eeas

  • 5 M Uni.-erst y, Dccie:

associa:ad wi:n :ne

'.ere 111 te no siin;ficant envir:n ental i ;a::; wer levels up to 2.MWt and l' censing Of research react:rs to :: crate asta:enents are recuired to be ritten for the
'a: no envir:nrental im;a::

issuance Of ::nstruction permits or c;e ating licenses for such facilities.

'a'e have determined that this generic evaidation is applicable to c;eration Of the University of Cal'fernia at Serkeley TRIGA reactor and that there arei no 5;ecial er different fea:cres which weuld preclude reliance en the gener c Ccnsequently, =e have Ceterednec that the cenclusion reached l

evaluatien.

in the generic evaluation is equally applicable :o his license renewa.eed net te prepared, an enviror.me.:al 'r:t:: s ateren r,r nerm:re, tased on car revie, f 5:ecific facili*y iters whien are corsidere ac:icn anc ;r.c t tel:w, wt have c:ntlucec ht:

a-tial e-vir n ental i :ac:, cis:ctsa d oint of
  1. e
  • ~1s lic!n q re ewal aC:i:n is i'siinificant fr:m the stan iavir:r-.en ai #i;act.

a 1

g*i9 is so s.

v3

i~elires
  • *."ans # !!' n I'nes en*e-ia; cr leavinc *.*e si e

'll u*;'"*y Ie'.*ss

.-a!!", s ! 8 P., e tetritity,.e'e:-cne

~~.a'e a#e *:

7e *: *r.:se re:virec f:r,.* ital

! * ; *.' e ;"a c e. !"e Oe'"a ;"a e 2 *0 1*e ** ;1*a:

~: se g ~!,
  • s -..,q

. s s e.s *

  • r
  • s. t.

ees

..

  • e

)

J m

C m. 5 s '.. C,. e m.... o v. e,......,.

,, -.,. e..:,.y s.a..

m.e.

s

i. c y e ) e t.

1 l..w*.

p./..e a. s e. r. e r 3. j w.. ig.-.. r..c...

' o..s.. - c. e, c. e.s.. d c....

v

..s 8

i s...

4 1.... r..n a w

..c....

  • d e. s..
s

+ a. c.c.

e..c.
a. $.e i. $ $. e. 2. c. s. 7.,..,

.e e.

i 1

w,a.

s.

3w..

6

)

.. e.< *. e. sk, y g. c. e. t t e..J. 2

  • 4. r..

....p

$ _,. e. : -,, n d. -.

.-.(

... },,... =..

3

h. a 3 4

.. e.

e..g e.
c. e.. (.

.c p e..e. es *y g. e ) c. s..

, (i. r.a fe

.s. g

.e..

.. g z e. r a.

ee:. n u.e

..+.(

.ic.

=

s

o. %.

r e.. '. r c ul a. c. '.. #. c i w.' *. =..,

c- < e =. s.. r - - k.

  • .=. ' =..=. m. i '. - : -. s. r c." i s..-. e. d e

3 e :. g.

.. s e. s. e..

e......

...e e.ecqa.r3

=

.e c

e

. s..e

.c..

..e q

e:

..g e. >.

. n.. e. i. y.

o.

i r :.1 e.. e. y i$ y. e z. :. s.

i3 :.. u. ;.. a e,. y...,:g')

c.

.. a.

..r..:e.

. a. a.

7 car:Us, tr.d no additic al constru: tic, is es e::ed curing the license rene a!

eA.

N

- s. e. l..

e

e. :.. f.. e
r. e e..

e w.e.g.eg) g.

G.e e.

.. e. r g e.. : e. g.* g.ese y,

r.,, 1 a e,,. ;, V :.. y

a. i. 2 a e a. s

.e I

s:ent activa ed sa :les ar.d the release Of "r;:n-4. fr:1 ne r:n activa:icn J...

+

c air in various tiposure facilities.

ine iscensae.s calc 3.au. ens anc cur 4

inde;endent analysis i-dicate that release cf 'r;:n-C aill ret exceed 1f c:ncentra.icns specified in 10 C.:R 20 limits f:r res:r'c:ed and for non.

j restricted areas which c:uld be cccupied.

9 Fur-her.cre, the direct radiaticn levels fr:e :his facility and frcm the 4j

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